مواد مشابهة: THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES /
- ANALYSIS OF SHIELD DESIGN ASPECT OF SEMI-INDUSTRIAL COBALT 60 GAMA IRRADIATION FACILITY AT IRPT BY MICRO-SHEILD 5.05 AND QAD-CGGP2 /
- AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
- CONCEPTUAL DESIGN OF VVER-1200 SPENT NUCLEAR FUEL DRY STORAGE CASK : A NEUTRONIC, RADIATION SHIELDING AND THERMAL ANALYSIS /
- ANALYSIS OF STRUCTURAL SAFETY PARAMETERS AND THERMAL BEHAVIOR OF THE FUEL ASSEMBLY OF A GENERIC VVER-1200 NUCLEAR REACTOR USING ANSYS /
- Nuclear reactor analysis /
- A NUMERICAL APROACH TO DESIGN AND DEVELOP PHYSICAL PROTECTION SYSTEM OF A NUCLEAR INSTALLATION /
موضوع: Nuclear Science and Engineering.
- ANALYSIS OF A PROBABILISTIC FRACTURE MECHANICS CODE FOR PRESSURIZED WATER REACTOR /
- AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
- DESIGN AND DEVELOPMENT OF A LOW COST AIRBORNE RADIATION MAPPING SYSTEM USING UNMANNED AERIAL VEHICLE (UAV) /
- THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES /
- A NUMERICAL APROACH TO DESIGN AND DEVELOP PHYSICAL PROTECTION SYSTEM OF A NUCLEAR INSTALLATION /
- A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
موضوع: This Thesis Paper of NSE in BSc Program.
- REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
- THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES /
- NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /
- OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
- ASSESSMENT OF NATURAL RADIONUCLIDES AND HEAVY METALS IN SOIL SAMPLES OF JAMUNA RIVER BASIN, BANGLADESH /
- CONCEPTUAL DESIGN OF VVER-1200 SPENT NUCLEAR FUEL DRY STORAGE CASK : A NEUTRONIC, RADIATION SHIELDING AND THERMAL ANALYSIS /